EP0183101A1 - Installation à énergie nucléaire à refroidissement par métal liquide avec générateurs de vapeur intégrés dans l'enceinte de sécurité - Google Patents

Installation à énergie nucléaire à refroidissement par métal liquide avec générateurs de vapeur intégrés dans l'enceinte de sécurité Download PDF

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Publication number
EP0183101A1
EP0183101A1 EP85114151A EP85114151A EP0183101A1 EP 0183101 A1 EP0183101 A1 EP 0183101A1 EP 85114151 A EP85114151 A EP 85114151A EP 85114151 A EP85114151 A EP 85114151A EP 0183101 A1 EP0183101 A1 EP 0183101A1
Authority
EP
European Patent Office
Prior art keywords
cells
safety enclosure
coolant
steam generators
cooled nuclear
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Withdrawn
Application number
EP85114151A
Other languages
German (de)
English (en)
Inventor
Günter Dipl.-Ing. Hahn
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Interatom Internationale Atomreaktorbau GmbH
Original Assignee
Interatom Internationale Atomreaktorbau GmbH
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Interatom Internationale Atomreaktorbau GmbH filed Critical Interatom Internationale Atomreaktorbau GmbH
Publication of EP0183101A1 publication Critical patent/EP0183101A1/fr
Withdrawn legal-status Critical Current

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention relates to a nuclear power plant according to the preamble of claim 1.
  • the scheme of such a nuclear power plant is e.g. B. from DE-A-24 45 553 known.
  • Sodium or a sodium alloy is preferably used as the primary and secondary coolant, while water is used as the tertiary coolant, which is evaporated in the heat exchangers which transmit the heat from the secondary to the tertiary cooling circuit and is then used as a working medium for operating power generators.
  • the steam represents a significant pressure energy potential that z. B. due to a larger steam generator leak to the eventual condensation leads to a considerable load on the enclosing building.
  • the safety containment of the reactor building need not be designed against high internal pressure loads and its ability to possibly remove the radioactivity contained in the reactor itself and in the primary circuit Safe retention is guaranteed even without the complex installation of a tight sheet metal lining.
  • the reactor building should be able to provide sufficient resistance to external influences, in particular an aircraft crash. This leads to reactor buildings of cylindrical and / or hemispherical shape, which in turn require that the steam generator buildings can only be arranged at a certain distance therefrom.
  • the pipes forming the secondary circuit become relatively long, which has a number of disadvantages: higher pressure loss - higher heat loss despite extensive insulation - more complex trace heating - larger number of pipe loops to compensate for the impeded thermal expansion - larger number of welds subject to inspection - larger coolant volume, which in turn forces drain containers etc. to be enlarged accordingly, as well as an increase in the construction volume required to accommodate the system.
  • the object of the present invention is to arrange the various components belonging to the cooling circuit of such a nuclear power plant in such a way that the above-mentioned. Disadvantages are avoided or minimized.
  • Non-radioactive parts of the plant that contain high-tension water or steam ie the steam generator with the necessary connection lines can therefore be arranged within the safety enclosure of the reactor building, because the cells surrounding them can withstand a pressure build-up taking place in them at any time, so that the former does not have any particular pressure loads must withstand inside; in a preferred embodiment defined by the second claim, in that possibilities for pressure relief from the cells are created through the safety enclosure into the atmosphere.
  • the individual components of the heat transfer circuits can then be arranged in the immediate vicinity of one another, which, as explained above, subsequently leads to considerable savings in plant costs.
  • a reactor tank 1 which is surrounded by a biological shield 2, is common to both types of plant.
  • the entire primary circuit including a pump 5 circulating the primary coolant is arranged within the reactor tank 1, as are intermediate heat exchangers 6, in which the primary circuit gives off its heat to the secondary circuit, which is also operated with sodium.
  • the primary pump 5 and the intermediate heat exchanger 6 are arranged outside the reactor tank 1.
  • the secondary circuit is maintained by further pumps 7 and closes steam generator 8 .
  • a in which water vapor is generated on the tertiary side, which is supplied to machines not shown here, preferably turbogenerators.
  • the above-mentioned system parts are arranged within a safety enclosure 3 made of concrete, which can withstand both external influences, such as an aircraft crash, and any internal activity releases that could be caused by possible leaks.
  • Secondary pumps 7 and steam generator 8 and the associated pipelines that is to say those parts of the plant which, in the event of accidents, could result in considerable energy releases are arranged in special cells 4 which are independent of the safety enclosure 3 and which are suitable in terms of their construction, such energy Resist releases in their interior, preferably in that they are provided with relief channels 42 which led through the wall of the safety enclosure 3 into the open and in normal operation z. B. ' are closed with rupture discs, not shown here.
  • the cells 4 are provided on their upper side with openings 41 which are closed with corresponding plugs during operation.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
EP85114151A 1984-11-19 1985-11-06 Installation à énergie nucléaire à refroidissement par métal liquide avec générateurs de vapeur intégrés dans l'enceinte de sécurité Withdrawn EP0183101A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3442236 1984-11-19
DE19843442236 DE3442236A1 (de) 1984-11-19 1984-11-19 Fluessigmetallgekuehlte kernenergieanlage mit in den sicherheitseinschluss integrierten dampferzeugern

Publications (1)

Publication Number Publication Date
EP0183101A1 true EP0183101A1 (fr) 1986-06-04

Family

ID=6250664

Family Applications (1)

Application Number Title Priority Date Filing Date
EP85114151A Withdrawn EP0183101A1 (fr) 1984-11-19 1985-11-06 Installation à énergie nucléaire à refroidissement par métal liquide avec générateurs de vapeur intégrés dans l'enceinte de sécurité

Country Status (2)

Country Link
EP (1) EP0183101A1 (fr)
DE (1) DE3442236A1 (fr)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2188472C2 (ru) * 2000-11-08 2002-08-27 Опытное Конструкторское Бюро "Гидропресс" Способ передачи тепловой энергии источника рабочему телу энергетической установки посредством жидкометаллического теплоносителя
RU2212066C1 (ru) * 2002-05-17 2003-09-10 Фгуп Окб "Гидропресс" Ядерный паропроизводящий агрегат с жидкометаллическим теплоносителем
RU2762391C1 (ru) * 2021-06-27 2021-12-20 Виталий Алексеевич Узиков Реакторная установка на быстрых нейтронах с пассивной системой охлаждения активной зоны

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2246028A1 (fr) * 1973-10-02 1975-04-25 Electricite De France

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2246028A1 (fr) * 1973-10-02 1975-04-25 Electricite De France

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
CONFERENCE SUR LA SURETE DES REACTEURS RAPIDES, 19.-23. Juli 1982, Lyon, FR; C. AYCOBERRY et al.: "L'après CREYS-MALVILLE: Les perspectives du projet de site intégré" *

Also Published As

Publication number Publication date
DE3442236A1 (de) 1986-05-22

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PUAI Public reference made under article 153(3) epc to a published international application that has entered the european phase

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Effective date: 19890531

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Inventor name: HAHN, GUENTER, DIPL.-ING.